Beryllium processing technology review for applications in plasma-facing components

Technical Report · Thu Jul 01 04:00:00 EDT 1993

DOI:https://doi.org/10.2172/10176907· OSTI ID:10176907

Castro, R G; Jacobson, L A; Stanek, P W

Materials research and development activities for the International Thermonuclear Experimental Reactor (ITER), i.e., the next generation fusion reactor, are investigating beryllium as the first-wall containment material for the reactor. Important in the selection of beryllium is the ability to process, fabricate and repair beryllium first-wall components using existing technologies. Two issues that will need to be addressed during the engineering design activity will be the bonding of beryllium tiles in high-heat-flux areas of the reactor, and the in situ repair of damaged beryllium tiles. The following review summarizes the current technology associated with welding and joining of beryllium to itself and other materials, and the state-of-the-art in plasma-spray technology as an in situ repair technique for damaged beryllium tiles. In addition, a review of the current status of beryllium technology in the former Soviet Union is also included.

• Research Organization: Los Alamos National Lab., NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 10176907
• Report Number(s): LA--12545-MS; ON: DE93018396
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360101
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480
BERYLLIUM
BRAZING
COMPONENT DEVELOPMENT
FABRICATION
FIRST WALL
HEAT TREATMENTS
ITER TOKAMAK
JOINING
MATERIALS STUDIES
PLASMA ARC SPRAYING
POROSITY
PREPARATION AND FABRICATION
REPAIR
RESEARCH PROGRAMS
TECHNOLOGY ASSESSMENT
THERMONUCLEAR REACTOR MATERIALS
USSR